ML19316A083
| ML19316A083 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/27/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thies A DUKE POWER CO. |
| References | |
| NUDOCS 7911210808 | |
| Download: ML19316A083 (1) | |
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UNITED STATES
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Yk MTOMIC ENERGY COMMISSION' / Di=tribution:
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WAZHIN OTON. D.C. 205/.5 AEC PDR (3)
Docket Files (3)/
er,rh e Mar 4h 27, 1970 DR Reading i
Docket Nos. 50-269 [ _ ___
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DRL Reading pWR-2-Reading -
3 Ca P. A. Mords Duke Power Compan7 F. Schroeder i
Power Building T.'R 7 11 son I '
422 South Church Street R. C. DeYoung Charlotte, North Carolina 28201 R. S. Boyd S. Levine Attention:
Mr. Aus tin C. Thies D. J. Skovholt Vice President L. Kornblith, CO (3)
Production & Operation DRL Branch Chiefs F. W. Karas (2)
Centlemen:
A. Schwencer We need additional in~fdr:dtionvco=plete our. review of your analysis of the ' loss-of-coolant accident for the Oconee Nuclear Station. The flow rates predicted by the analyses of the syste= blowdown and core heatup for the spectru= of cold-leg break si::es should be provided and the core heat transfer coef ficients used should be identified. A comprehensive su==ary should be provided of the analytical methods and computer codes used in the analysis of the thermal-hydraulic aspects of the loss-of-coolant accident.
This su==ary should include:
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(a) a description of each code (purpose', fundamental assumptions, basic equations, nature _of-input and output) ;
(b) a description of the procedures used in applying the output results of one computer code as input information to another code; (c) identification of the codes used in calculating the results shown in various tables and figures in the FSAR; (d) a quantitative discussion of the bases for selection of the input parameters used in the FLASH code to =odel the pri=ary systa=,
and justification that the selected para eters lead to conservative
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results.
Please contact us-if you desire any discussion or clarification of the infor=ation requested by this letter.
- Sincerely, f
Original Signed by f,eter A. Morris' Peter A. Morris, Director
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Division of Reactor Licensing PWR-2(DRL P
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